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INL makes first fuel for Molten Chloride Reactor Experiment
Idaho National Laboratory has announced the creation of the first batch of enriched uranium chloride fuel salt for the Molten Chloride Reactor Experiment (MCRE). INL said that its fuel production team delivered the first fuel salt batch at the end of September, and it intends to produce four additional batches by March 2026. MCRE will require a total of 72–75 batches of fuel salt for the reactor to go critical.
M. Zadro, S. Blagus, Ð. Miljanić, D. Rendić
Nuclear Science and Engineering | Volume 95 | Number 1 | January 1987 | Pages 79-81
Technical Note | doi.org/10.13182/NSE87-A20434
Articles are hosted by Taylor and Francis Online.
The sum of the 9Be(n, t0)7Li and 9Be(n, t1)7Li reaction cross sections was measured at an incident neutron energy of 14.6 MeV using a counter telescope for triton detection. The angular distribution of these reactions was obtained for the center of mass angles up to 90 deg. It is nearly isotropic. Assuming a forward-backward symmetry of the angular distribution, the total cross section for the (n, t) reaction on 9Be is found to be 24 ± 2 mb. This result compares favorably with the data from the tritium beta-counting experiments.